Finite Element Analysis of Thermal Conducting Property of UO2 Composite Fuel Pellet

被引：0
|
作者：
Liu C. [1 ]
Jin E. [2 ]
Xu L. [1 ]
Wang W. [1 ]
机构：
[1] Beijing Research Institute of Chemical Engineering and Metallurgy, CNNC, Beijing
[2] Aerospace Research Institute of Materials & Processing Technology, Beijing
来源：
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2019年 / 53卷 / 03期
关键词：
Composite fuel pellet; Finite element analysis; Pressurized water reactor; Thermal conducting property;
D O I：
10.7538/yzk.2018.youxian.0659
中图分类号：
学科分类号：
摘要：
Nowadays, many countries start to develop advanced UO2 composite fuel pellet that can be used in the pressurized water reactor (PWR) by adding a few amounts of the second phase materials with high thermal conducting. In this paper, the influences of key structural parameters on the thermal conducting properties of advanced UO2 composite fuel pellet were investigated by finite element analysis method. The results show that a few amounts of the second phase materials can reduce the center line temperature of the fuel pellets significantly. The type, amount and distribution form of the second phase have important influence on the thermal conducting property of advanced UO2 composite fuel pellet. © 2019, Editorial Board of Atomic Energy Science and Technology. All right reserved.
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页码：511 / 517
页数：6
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  • [1] Carbajo J.J., Yoder G.L., Popov S.G., Et al., A review of the thermophysical properties of MOX and UO<sub>2</sub> fuels, Journal of Nuclear Materials, 299, 3, pp. 181-198, (2001)
  • [2] Lyons M.F., Boyle R.F., Davies J.H., Et al., UO<sub>2</sub> properties affecting performance, Nuclear Engineering and Design, 21, 2, pp. 167-199, (1971)
  • [3] Michel B., Sercombe J., Thouvenin G., Et al., 3D fuel cracking modelling in pellet cladding mechanical interaction, Engineering Fracture Mechanics, 75, 11, pp. 3581-3598, (2008)
  • [4] Hiernaut J.P., Wiss T., Colle J.Y., Et al., Fission product release and microstructure changes during laboratory annealing of a very high burn-up fuel specimen, Journal of Nuclear Materials, 377, 2, pp. 313-324, (2008)
  • [5] Yeo S., Baney R., Subhash G., Et al., The influence of SiC particle size and volume fraction on the thermal conductivity of spark plasma sintered UO<sub>2</sub>-SiC composites, Journal of Nuclear Materials, 442, 1-3, pp. 245-252, (2013)
  • [6] Sarma K.H., Fourcade J., Lee S.G., Et al., New processing methods to produce silicon carbide and beryllium oxide inert matrix and enhanced thermal conductivity oxide fuels, Journal of Nuclear Materials, 352, 1-3, pp. 324-333, (2006)
  • [7] Yeo S., Mckenna E., Baney R., Et al., Enhanced thermal conductivity of uranium dioxide-silicon carbide composite fuel pellets prepared by spark plasma sintering (SPS), Journal of Nuclear Materials, 433, 1-3, pp. 66-73, (2013)
  • [8] Kutty Tr G., Khan K.B., Somayajulu P.S., Et al., Development of CAP process for fabrication of ThO<sub>2</sub>-UO<sub>2</sub> fuels, Part Ⅰ: Fabrication and densification behaviour, Journal of Nuclear Materials, 373, 1-3, pp. 299-308, (2008)
  • [9] Savchenko A., Konovalov I., Vatulin A., Dispersion type zirconium matrix fuels fabricated by capillary impregnation method, Journal of Nuclear Materials, 362, 2-3, pp. 356-363, (2007)
  • [10] Lucuta P.G., Matzke H., Hastings I.J., A pragmatic approach to modelling thermal conductivity of irradiated UO<sub>2</sub> fuel: Review and recommendations, Journal of Nuclear Materials, 232, 2-3, pp. 166-180, (1996)
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